Systems and methods for radial and axial stability control of an frc plasma

ABSTRACT

Systems and methods are provided that facilitate stability of an FRC plasma in both radial and axial directions and axial position control of an FRC plasma along the symmetry axis of an FRC plasma chamber. The systems and methods exploit an axially unstable equilibria of the FRC plasma to enforce radial stability, while stabilizing or controlling the axial instability. The systems and methods provide feedback control of the FRC plasma axial position independent of the stability properties of the plasma equilibrium by acting on the voltages applied to a set of external coils concentric with the plasma and using a non-linear control technique.

CROSS-REFERENCE TO RELATED APPLICATIONS

The subject application is a continuation of U.S. patent application Ser. No. 17/525,437, filed May 10, 2018, which is a continuation of U.S. patent application Ser. No. 15/976,532, filed May 10, 2018, now U.S. Pat. No. 11,217,351, which is a continuation of International Patent Application No. PCT/US16/61730, filed Nov. 13, 2016, which claims priority to U.S. Provisional Patent Application No. 62/309,344, filed on Mar. 16, 2016, and U.S. Provisional Patent Application No. 62/255,258, filed on Nov. 13, 2015, all of which are incorporated by reference herein in their entireties for all purposes.

FIELD

The subject matter described herein relates generally to magnetic plasma confinement systems having a field reversed configuration (FRC) and, more particularly, to systems and methods that facilitate stability of an FRC plasma in both radial and axial directions and the control of the FRC plasma position along the symmetry axis of an FRC plasma confinement chamber.

BACKGROUND INFORMATION

The Field Reversed Configuration (FRC) belongs to the class of magnetic plasma confinement topologies known as compact toroids (CT). It exhibits predominantly poloidal magnetic fields and possesses zero or small self-generated toroidal fields (see M. Tuszewski, Nucl. Fusion 28, 2033 (1988)). The attractions of such a configuration are its simple geometry for ease of construction and maintenance, a natural unrestricted divertor for facilitating energy extraction and ash removal, and very high β (β is the ratio of the average plasma pressure to the average magnetic field pressure inside the FRC), i.e., high power density. The high β nature is advantageous for economic operation and for the use of advanced, aneutronic fuels such as D-He³ and p-B¹¹.

FRC devices are closed, high-vacuum devices relying on a magnetic field to confine high-temperature plasmas for, among others, the purpose of generating thermonuclear fusion energy. A component of the magnetic field must necessarily be produced by an intense toroidal current in the plasma, which interacts with the magnetic field produced by external coils to the plasma. In contrast with other magnetic confinement devices, FRC devices have no external coils to produce a toroidal field. A typical FRC plasma resembles an ellipsoid of revolution with its axis along the external coil axis. The ellipsoid boundary is the plasma separatrix, which bounds a compact toroidal plasma with its symmetry axis along the revolution axis of the ellipsoid.

Due the lack of toroidal magnetic field, FRC plasmas are prone to axisymmetry breakings that may lead to increased energy, density and confinement losses if no corrective actions are taken. The most basic instability relates to the fact that in an FRC plasma the plasma current flows in opposite direction to the external coil current, which generates a torque which works in the direction to align the plasma current loop with the external field (tilt instability). Other axisymmetry breakings relate to the plasma revolution axis shifting radially (radial shift), an elliptical deformation of the FRC waist (rotational mode) a combination of radial shift and rotation (wobble mode), plasma microturbulence, and others. These axisymmetry breakings, also known as plasma instabilities, must be avoided in order to have a good confinement of the plasma mass and energy.

One of the solutions proposed to achieve stability in the radial direction is based on the fact that FRC equilibria contains solutions in which the plasma position is either stable in the axial direction at the expense of being unstable in the transverse or radial direction, or stable in the radial direction at the expense of being axially unstable, but not both at the same time. To the first order, an equilibrium where the plasma position is transversally stable has the desired property of being axisymmetric, at the expense of being axially unstable. The axial position instability, however, can be actively controlled using a set of external axisymmetric coils to obtain stability in both axial and radial directions.

In light of the foregoing, it is, therefore, desirable to provide systems and methods that facilitate the control of the axial position of an FRC plasma in a way independent of the axial stability properties of its equilibrium. This is important because the equilibrium may have to transit between an axially stable and unstable equilibria on different phases of the FRC discharge, for instance if the axial instability scenario is temporarily lost and recovered during the plasma discharge.

SUMMARY

The present embodiments provided herein are directed to systems and methods that facilitate stability of an FRC plasma in both radial and axial directions and axial position control of an FRC plasma along the symmetry axis of an FRC plasma confinement chamber independent of the axial stability properties of the FRC plasma's equilibrium. To the first order, an equilibrium where the plasma position is transversally or radially stable has the desired property of being axisymmetric, at the expense of being axially unstable. The axial position instability, however, is actively controlled using a set of external axisymmetric coils that control the FRC plasma axial position.

The embodiments presented herein exploit an axially unstable equilibria of the FRC to enforce radial stability, while stabilizing or controlling the axial instability. In this way, stability in both axial and radial directions can be obtained. The control methodology is designed to alter the external or equilibrium magnetic field to make the FRC plasma radially or transversally stable at the expense of being axially unstable, and then act on the radial field coil current in order to expeditiously restore the FRC plasma position towards the mid-plane while minimizing overshooting and/or oscillations around the mid-plane of the confinement chamber. The advantage of this solution is that it reduces the complexity of the actuators required for control. Compared with the conventional solutions with multiple degrees of freedom, the methodology of the embodiment presented herein reduces the complexity to a control problem along the FRC plasma revolution axis having one degree of freedom.

The systems and methods described herein advantageously provide: feedback control of the FRC plasma axial position by acting on the voltages applied to a set of external coils concentric with the plasma; feedback control of the FRC axial position using a non-linear control technique; and, feedback control of the FRC axial position independently of the stability properties of the plasma equilibrium. This is independence is advantageous because the equilibrium may have to transit between an axially stable and unstable equilibria on different phases of the FRC discharge, for instance if the axial instability scenario is temporarily lost and recovered during the plasma discharge.

The systems, methods, features and advantages of the example embodiments will be or will become apparent to one with skill in the art upon examination of the following figures and detailed description. It is intended that all such additional methods, features and advantages be included within this description, and be protected by the accompanying claims. It is also intended that the claims are not limited to require the details of the example embodiments.

BRIEF DESCRIPTION OF THE FIGURES

The accompanying drawings, which are included as part of the present specification, illustrate the presently example embodiments and, together with the general description given above and the detailed description of the example embodiments given below, serve to explain and teach the principles of the present invention.

FIG. 1 illustrates particle confinement in the present FRC system under a high performance FRC regime (HPF) versus under a conventional FRC regime (CR), and versus other conventional FRC experiments.

FIG. 2 illustrates the components of the present FRC system and the magnetic topology of an FRC producible in the present FRC system.

FIG. 3A illustrates the basic layout of the present FRC system as viewed from the top, including the preferred arrangement of neutral beams, electrodes, plasma guns, mirror plugs and pellet injector.

FIG. 3B illustrates the central confinement vessel as viewed from the top and showing the neutral beams arranged at an angle normal to the major axis of symmetry in the central confinement vessel.

FIG. 3C illustrates the central confinement vessel as viewed from the top and showing the neutral beams arranged at an angle less than normal to the major axis of symmetry in the central confinement vessel and directed to inject particles toward the mid-plane of the central confinement vessel.

FIGS. 3D and 3E illustrate top and perspective views, respectively, of the basic layout of an alternative embodiment of the present FRC system, including the preferred arrangement of the central confinement vessel, formation section, inner and outer divertors, neutral beams arranged at an angle less than normal to the major axis of symmetry in the central confinement vessel, electrodes, plasma guns and mirror plugs.

FIG. 4 illustrates a schematic of the components of a pulsed power system for the formation sections.

FIG. 5 illustrates an isometric view of an individual pulsed power formation skid.

FIG. 6 illustrates an isometric view of a formation tube assembly.

FIG. 7 illustrates a partial sectional isometric view of neutral beam system and key components.

FIG. 8 illustrates an isometric view of the neutral beam arrangement on confinement chamber.

FIG. 9 illustrates a partial sectional isometric view of a preferred arrangement of the Ti and Li gettering systems.

FIG. 10 illustrates a partial sectional isometric view of a plasma gun installed in the divertor chamber. Also shown are the associated magnetic mirror plug and a divertor electrode assembly.

FIG. 11 illustrates a preferred layout of an annular bias electrode at the axial end of the confinement chamber.

FIG. 12 illustrates the evolution of the excluded flux radius in the FRC system obtained from a series of external diamagnetic loops at the two field reversed theta pinch formation sections and magnetic probes embedded inside the central metal confinement chamber. Time is measured from the instant of synchronized field reversal in the formation sources, and distance z is given relative to the axial midplane of the machine.

FIGS. 13A, 13B, 13C, and 13D illustrate data from a representative non-HPF, un-sustained discharge on the present FRC system. Shown as functions of time are (FIG. 13A) excluded flux radius at the midplane, (FIG. 13B) 6 chords of line-integrated density from the midplane CO2 interferometer, (FIG. 13C) Abel-inverted density radial profiles from the CO2 interferometer data, and (FIG. 13D) total plasma temperature from pressure balance.

FIG. 14 illustrates the excluded flux axial profiles at selected times for the same discharge of the present FRC system shown in FIGS. 13A, 13B, 13C and 13D.

FIG. 15 illustrates an isometric view of the saddle coils mounted outside of the confinement chamber.

FIGS. 16A, 16B, 16C and 16D illustrate the correlations of FRC lifetime and pulse length of injected neutral beams. As shown, longer beam pulses produce longer lived FRCs.

FIGS. 17A, 17B, 17C and 17D illustrate the individual and combined effects of different components of the FRC system on FRC performance and the attainment of the HPF regime.

FIGS. 18A, 18B, 18C and 18D illustrate data from a representative HPF, un-sustained discharge on the present FRC system. Shown as functions of time are (FIG. 18A) excluded flux radius at the midplane, (FIG. 18B) 6 chords of line-integrated density from the midplane CO2 interferometer, (FIG. 18C) Abel-inverted density radial profiles from the CO2 interferometer data, and (FIG. 18D) total plasma temperature from pressure balance.

FIG. 19 illustrates flux confinement as a function of electron temperature (T_(e)). It represents a graphical representation of a newly established superior scaling regime for HPF discharges.

FIG. 20 illustrates the FRC lifetime corresponding to the pulse length of non-angled and angled injected neutral beams.

FIGS. 21A and 21B illustrate the basic layout of a compact toroid (CT) injector.

FIGS. 22A and 22B illustrate the central confinement vessel showing the CT injector mounted thereto.

FIGS. 23A and 23B illustrate the basic layout of an alternative embodiment of the CT injector having a drift tube coupled thereto.

FIG. 24 is a schematic of illustrating an axial position control mechanism of an FRC plasma within a confining vessel (CV).

FIG. 25 is a flow diagram of a generic sliding mode control scheme.

FIG. 26 is a composite graph of examples of a sliding mode axial position control simulation.

FIG. 27 is a composite graph of examples of a sliding mode axial position control simulation.

It should be noted that the figures are not necessarily drawn to scale and that elements of similar structures or functions are generally represented by like reference numerals for illustrative purposes throughout the figures. It also should be noted that the figures are only intended to facilitate the description of the various embodiments described herein. The figures do not necessarily describe every aspect of the teachings disclosed herein and do not limit the scope of the claims.

DETAILED DESCRIPTION

The present embodiments provided herein are directed to systems and methods that facilitate stability of an FRC plasma in both radial and axial directions and axial position control of an FRC plasma along the symmetry axis of an FRC plasma confinement chamber independent of the axial stability properties of the FRC plasma's equilibrium. Representative examples of the embodiments described herein, which examples utilize many of these additional features and teachings both separately and in combination, will now be described in further detail with reference to the attached drawings. This detailed description is merely intended to teach a person of skill in the art further details for practicing preferred aspects of the present teachings and is not intended to limit the scope of the invention. Therefore, combinations of features and steps disclosed in the following detail description may not be necessary to practice the invention in the broadest sense, and are instead taught merely to particularly describe representative examples of the present teachings.

Moreover, the various features of the representative examples and the dependent claims may be combined in ways that are not specifically and explicitly enumerated in order to provide additional useful embodiments of the present teachings. In addition, it is expressly noted that all features disclosed in the description and/or the claims are intended to be disclosed separately and independently from each other for the purpose of original disclosure, as well as for the purpose of restricting the claimed subject matter independent of the compositions of the features in the embodiments and/or the claims. It is also expressly noted that all value ranges or indications of groups of entities disclose every possible intermediate value or intermediate entity for the purpose of original disclosure, as well as for the purpose of restricting the claimed subject matter.

Conventional solutions to FRC instabilities typically provide stability in the axial direction at the expense of being unstable in the radial direction, or stability in the radial direction at the expense of being axially unstable, but not stability in both directions at the same time. To the first order, an equilibrium where the plasma position is transversally or radially stable has the desired property of being axisymmetric, at the expense of being axially unstable. In view of the foregoing, the embodiments provided herein are directed to systems and methods that facilitate stability of an FRC plasma in both radial and axial directions and axial position control of an FRC plasma along the symmetry axis of an FRC plasma confinement chamber independent of the axial stability properties of the FRC plasma's equilibrium. The axial position instability, however, is actively controlled using a set of external axisymmetric coils that control the FRC plasma axial position. The systems and methods provide feedback control of the FRC plasma axial position independent of the stability properties of the plasma equilibrium by acting on the voltages applied to a set of external coils concentric with the plasma and using a non-linear control technique.

The embodiments presented herein exploit an axially unstable equilibria of the FRC to enforce radial stability, while stabilizing or controlling the axial instability. In this way, stability in both axial and radial directions can be obtained. The control methodology is designed to alter the external or equilibrium magnetic field to make the FRC plasma radially or transversally stable at the expense of being axially unstable, and then act on the radial field coil current in order to expeditiously restore the FRC plasma position towards the mid-plane while minimizing overshooting and/or oscillations around the mid-plane of the confinement chamber. The advantage of this solution is that it reduces the complexity of the actuators required for control. Compared with the conventional solutions with multiple degrees of freedom, the methodology of the embodiment presented herein reduces the complexity to a control problem along the FRC plasma revolution axis having one degree of freedom.

The combination of waveforms in coil currents, fueling and neutral beam power that result into an axially unstable plasma define the plasma control scenario that sets the plasma into an axial unstable situation. The scenario can be pre-programmed using prior knowledge of simulations or experiments, or feedback controlled to maintain an equilibrium that is axially unstable. The plasma position should be controlled during the discharges independently of the stability properties of the equilibrium, e.g. the control scheme should work for either axially stable or axially unstable plasmas, up to a limit. The most axially unstable plasma that can be controlled has a growth time comparable to the skin time of the vessel.

Before turning to the systems and methods that facilitate stability of an FRC plasma in both radial and axial directions and axial position control of an FRC plasma along the symmetry axis of an FRC plasma confinement chamber, a discussion of systems and methods for forming and maintaining high performance FRCs with superior stability as well as superior particle, energy and flux confinement over conventional FRCs is provided. Such high performance FRCs provide a pathway to a whole variety of applications including compact neutron sources (for medical isotope production, nuclear waste remediation, materials research, neutron radiography and tomography), compact photon sources (for chemical production and processing), mass separation and enrichment systems, and reactor cores for fusion of light nuclei for the future generation of energy.

Various ancillary systems and operating modes have been explored to assess whether there is a superior confinement regime in FRCs. These efforts have led to breakthrough discoveries and the development of a High Performance FRC paradigm described herein. In accordance with this new paradigm, the present systems and methods combine a host of novel ideas and means to dramatically improve FRC confinement as illustrated in FIG. 1 as well as provide stability control without negative side-effects. As discussed in greater detail below, FIG. 1 depicts particle confinement in an FRC system 10 described below (see FIGS. 2 and 3 ), operating in accordance with a High Performance FRC regime (HPF) for forming and maintaining an FRC versus operating in accordance with a conventional regime CR for forming and maintaining an FRC, and versus particle confinement in accordance with conventional regimes for forming and maintaining an FRC used in other experiments. The present disclosure will outline and detail the innovative individual components of the FRC system 10 and methods as well as their collective effects.

FRC System Vacuum System

FIGS. 2 and 3A depict a schematic of the present FRC system 10. The FRC system 10 includes a central confinement vessel 100 surrounded by two diametrically opposed reversed-field-theta-pinch formation sections 200 and, beyond the formation sections 200, two divertor chambers 300 to control neutral density and impurity contamination. The present FRC system 10 was built to accommodate ultrahigh vacuum and operates at typical base pressures of 10-8 torr. Such vacuum pressures require the use of double-pumped mating flanges between mating components, metal O-rings, high purity interior walls, as well as careful initial surface conditioning of all parts prior to assembly, such as physical and chemical cleaning followed by a 24 hour 250° C. vacuum baking and Hydrogen glow discharge cleaning.

The reversed-field-theta-pinch formation sections 200 are standard field-reversed-theta-pinches (FRTPs), albeit with an advanced pulsed power formation system discussed in detail below (see FIGS. 4 through 6 ). Each formation section 200 is made of standard opaque industrial grade quartz tubes that feature a 2 millimeter inner lining of ultrapure quartz. The confinement chamber 100 is made of stainless steel to allow a multitude of radial and tangential ports; it also serves as a flux conserver on the timescale of the experiments described below and limits fast magnetic transients. Vacuums are created and maintained within the FRC system 10 with a set of dry scroll roughing pumps, turbo molecular pumps and cryo pumps.

Magnetic System

The magnetic system 400 is illustrated in FIGS. 2 and 3A. FIG. 2 , amongst other features, illustrates an FRC magnetic flux and density contours (as functions of the radial and axial coordinates) pertaining to an FRC 450 producible by the FRC system 10. These contours were obtained by a 2-D resistive Hall-MHD numerical simulation using code developed to simulate systems and methods corresponding to the FRC system 10, and agree well with measured experimental data. As seen in FIG. 2 , the FRC 450 consists of a torus of closed field lines at the interior 453 of the FRC 450 inside a separatrix 451, and of an annular edge layer 456 on the open field lines 452 just outside the separatrix 451. The edge layer 456 coalesces into jets 454 beyond the FRC length, providing a natural divertor.

The main magnetic system 410 includes a series of quasi-dc coils 412, 414, and 416 that are situated at particular axial positions along the components, i.e., along the confinement chamber 100, the formation sections 200 and the divertors 300, of the FRC system 10. The quasi-dc coils 412, 414 and 416 are fed by quasi-dc switching power supplies and produce basic magnetic bias fields of about 0.1 T in the confinement chamber 100, the formation sections 200 and the divertors 300. In addition to the quasi-dc coils 412, 414 and 416, the main magnetic system 410 includes quasi-dc mirror coils 420 (fed by switching supplies) between either end of the confinement chamber 100 and the adjacent formation sections 200. The quasi-dc mirror coils 420 provide magnetic mirror ratios of up to 5 and can be independently energized for equilibrium shaping control. In addition, mirror plugs 440, are positioned between each of the formation sections 200 and divertors 300. The mirror plugs 440 comprise compact quasi-dc mirror coils 430 and mirror plug coils 444. The quasi-dc mirror coils 430 include three coils 432, 434 and 436 (fed by switching supplies) that produce additional guide fields to focus the magnetic flux surfaces 455 towards the small diameter passage 442 passing through the mirror plug coils 444. The mirror plug coils 444, which wrap around the small diameter passage 442 and are fed by LC pulsed power circuitry, produce strong magnetic mirror fields of up to 4 T. The purpose of this entire coil arrangement is to tightly bundle and guide the magnetic flux surfaces 455 and end-streaming plasma jets 454 into the remote chambers 310 of the divertors 300. Finally, a set of saddle-coil “antennas” 460 (see FIG. 15 ) are located outside the confinement chamber 100, two on each side of the mid-plane, and are fed by dc power supplies. The saddle-coil antennas 460 can be configured to provide a quasi-static magnetic dipole or quadrupole field of about 0.01 T for controlling rotational instabilities and/or electron current control. The saddle-coil antennas 460 can flexibly provide magnetic fields that are either symmetric or antisymmetric about the machine's midplane, depending on the direction of the applied currents.

Pulsed Power Formation Systems

The pulsed power formation systems 210 operate on a modified theta-pinch principle. There are two systems that each power one of the formation sections 200. FIGS. 4 through 6 illustrate the main building blocks and arrangement of the formation systems 210. The formation system 210 is composed of a modular pulsed power arrangement that consists of individual units (=skids) 220 that each energize a sub-set of coils 232 of a strap assembly 230 (=straps) that wrap around the formation quartz tubes 240. Each skid 220 is composed of capacitors 221, inductors 223, fast high current switches 225 and associated trigger 222 and dump circuitry 224. In total, each formation system 210 stores between 350-400 kJ of capacitive energy, which provides up to 35 GW of power to form and accelerate the FRCs. Coordinated operation of these components is achieved via a state-of-the-art trigger and control system 222 and 224 that allows synchronized timing between the formation systems 210 on each formation section 200 and minimizes switching jitter to tens of nanoseconds. The advantage of this modular design is its flexible operation: FRCs can be formed in-situ and then accelerated and injected (=static formation) or formed and accelerated at the same time (=dynamic formation).

Neutral Beam Injectors

Neutral atom beams 600 are deployed on the FRC system 10 to provide heating and current drive as well as to develop fast particle pressure. As shown in FIGS. 3A, 3B and 8 , the individual beam lines comprising neutral atom beam injector systems 610 and 640 are located around the central confinement chamber 100 and inject fast particles tangentially to the FRC plasma (and perpendicular or at an angel normal to the major axis of symmetry in the central confinement vessel 100) with an impact parameter such that the target trapping zone lies well within the separatrix 451 (see FIG. 2 ). Each injector system 610 and 640 is capable of injecting up to 1 MW of neutral beam power into the FRC plasma with particle energies between 20 and 40 keV. The systems 610 and 640 are based on positive ion multi-aperture extraction sources and utilize geometric focusing, inertial cooling of the ion extraction grids and differential pumping. Apart from using different plasma sources, the systems 610 and 640 are primarily differentiated by their physical design to meet their respective mounting locations, yielding side and top injection capabilities. Typical components of these neutral beam injectors are specifically illustrated in FIG. 7 for the side injector systems 610. As shown in FIG. 7 , each individual neutral beam system 610 includes an RF plasma source 612 at an input end (this is substituted with an arc source in systems 640) with a magnetic screen 614 covering the end. An ion optical source and acceleration grids 616 is coupled to the plasma source 612 and a gate valve 620 is positioned between the ion optical source and acceleration grids 616 and a neutralizer 622. A deflection magnet 624 and an ion dump 628 are located between the neutralizer 622 and an aiming device 630 at the exit end. A cooling system comprises two cryo-refrigerators 634, two cryopanels 636 and a LN2 shroud 638. This flexible design allows for operation over a broad range of FRC parameters.

An alternative configuration for the neutral atom beam injectors 600 is that of injecting the fast particles tangentially to the FRC plasma, but with an angle A less than 90° relative to the major axis of symmetry in the central confinement vessel 100. These types of orientation of the beam injectors 615 are shown in FIGS. 3C, 3D and 3E. In addition, the beam injectors 615 may be oriented such that the beam injectors 615 on either side of the mid-plane of the central confinement vessel 100 inject their particles towards the mid-plane. Finally, the axial position of these beam systems 600 may be chosen closer to the mid-plane. These alternative injection embodiments facilitate a more central fueling option, which provides for better coupling of the beams and higher trapping efficiency of the injected fast particles. Furthermore, depending on the angle and axial position, this arrangement of the beam injectors 615 allows more direct and independent control of the axial elongation and other characteristics of the FRC 450. For instance, injecting the beams at a shallow angle A relative to the vessel's major axis of symmetry will create an FRC plasma with longer axial extension and lower temperature while picking a more perpendicular angle A will lead to an axially shorter but hotter plasma. In this fashion the injection angle A and location of the beam injectors 615 can be optimized for different purposes. In addition, such angling and positioning of the beam injectors 615 can allow beams of higher energy (which is generally more favorable for depositing more power with less beam divergence) to be injected into lower magnetic fields than would otherwise be necessary to trap such beams. This is due to the fact that it is the azimuthal component of the energy that determines fast ion orbit scale (which becomes progressively smaller as the injection angle relative to the vessel's major axis of symmetry is reduced at constant beam energy). Furthermore, angled injection towards the mid-plane and with axial beam positions close to the mid-plane improves beam-plasma coupling, even as the FRC plasma shrinks or otherwise axially contracts during the injection period.

Turning to FIGS. 3D and 3E, another alternative configuration includes inner divertors 302 in addition to the angled beam injectors 615. The inner divertors 302 are positioned between the formation sections 200 and the confinement chamber 100, and are configured and operate substantially similar to the outer divertors 300. The inner divertors 302, which include fast switching magnetic coils therein, are effectively inactive during the formation process to enable the formation FRCs to pass through the inner divertors 302 as the formation FRCs translate toward the mid-plane of the confinement chamber 100. Once the formation FRCs pass through the inner divertors 302 into the confinement chamber 100, the inner divertors are activated to operate substantially similar to the outer divertors and isolate the confinement chamber 100 from the formation sections 200.

Pellet Injector

To provide a means to inject new particles and better control FRC particle inventory, a 12-barrel pellet injector 700 (see e.g. I. Vinyar et al., “Pellet Injectors Developed at PELIN for JET, TAE, and HL-2A,” Proceedings of the 26^(th) Fusion Science and Technology Symposium, 09/27 to 10/01 (2010)) is utilized on FRC system 10. FIG. 3A illustrates the layout of the pellet injector 700 on the FRC system 10. The cylindrical pellets (D˜1 mm, L˜1-2 mm) are injected into the FRC with a velocity in the range of 150-250 km/s. Each individual pellet contains about 5×10¹⁹ hydrogen atoms, which is comparable to the FRC particle inventory.

Gettering Systems

It is well known that neutral halo gas is a serious problem in all confinement systems. The charge exchange and recycling (release of cold impurity material from the wall) processes can have a devastating effect on energy and particle confinement. In addition, any significant density of neutral gas at or near the edge will lead to prompt losses of or at least severely curtail the lifetime of injected large orbit (high energy) particles (large orbit refers to particles having orbits on the scale of the FRC topology or at least orbit radii much larger than the characteristic magnetic field gradient length scale)—a fact that is detrimental to all energetic plasma applications, including fusion via auxiliary beam heating.

Surface conditioning is a means by which the detrimental effects of neutral gas and impurities can be controlled or reduced in a confinement system. To this end the FRC system 10 provided herein employs Titanium and Lithium deposition systems 810 and 820 that coat the plasma facing surfaces of the confinement chamber (or vessel) 100 and diverters 300 and 302 with films (tens of micrometers thick) of Ti and/or Li. The coatings are achieved via vapor deposition techniques. Solid Li and/or Ti are evaporated and/or sublimated and sprayed onto nearby surfaces to form the coatings. The sources are atomic ovens with guide nozzles (in case of Li) 822 or heated spheres of solid with guide shrouding (in case of Ti) 812. Li evaporator systems typically operate in a continuous mode while Ti sublimators are mostly operated intermittently in between plasma operation. Operating temperatures of these systems are above 600° C. to obtain fast deposition rates. To achieve good wall coverage, multiple strategically located evaporator/sublimator systems are necessary. FIG. 9 details a preferred arrangement of the gettering deposition systems 810 and 820 in the FRC system 10. The coatings act as gettering surfaces and effectively pump atomic and molecular hydrogenic species (H and D). The coatings also reduce other typical impurities such as Carbon and Oxygen to insignificant levels.

Mirror Plugs

As stated above, the FRC system 10 employs sets of mirror coils 420, 430, and 444 as shown in FIGS. 2 and 3A. A first set of mirror coils 420 is located at the two axial ends of the confinement chamber 100 and is independently energized from the confinement coils 412, 414 and 416 of the main magnetic system 410. The first set of mirror coils 420 primarily helps to steer and axially contain the FRC 450 during merging and provides equilibrium shaping control during sustainment. The first mirror coil set 420 produces nominally higher magnetic fields (around 0.4 to 0.5 T) than the central confinement field produced by the central confinement coils 412. The second set of mirror coils 430, which includes three compact quasi-dc mirror coils 432, 434 and 436, is located between the formation sections 200 and the divertors 300 and are driven by a common switching power supply. The mirror coils 432, 434 and 436, together with the more compact pulsed mirror plug coils 444 (fed by a capacitive power supply) and the physical constriction 442 form the mirror plugs 440 that provide a narrow low gas conductance path with very high magnetic fields (between 2 to 4 T with rise times of about 10 to 20 ms). The most compact pulsed mirror coils 444 are of compact radial dimensions, bore of 20 cm and similar length, compared to the meter-plus-scale bore and pancake design of the confinement coils 412, 414 and 416. The purpose of the mirror plugs 440 is multifold: (1) The coils 432, 434, 436 and 444 tightly bundle and guide the magnetic flux surfaces 452 and end-streaming plasma jets 454 into the remote divertor chambers 300. This assures that the exhaust particles reach the divertors 300 appropriately and that there are continuous flux surfaces 455 that trace from the open field line 452 region of the central FRC 450 all the way to the divertors 300. (2) The physical constrictions 442 in the FRC system 10, through which that the coils 432, 434, 436 and 444 enable passage of the magnetic flux surfaces 452 and plasma jets 454, provide an impediment to neutral gas flow from the plasma guns 350 that sit in the divertors 300. In the same vein, the constrictions 442 prevent back-streaming of gas from the formation sections 200 to the divertors 300 thereby reducing the number of neutral particles that has to be introduced into the entire FRC system 10 when commencing the startup of an FRC. (3) The strong axial mirrors produced by the coils 432, 434, 436 and 444 reduce axial particle losses and thereby reduce the parallel particle diffusivity on open field lines.

In the alternative configuration shown in FIGS. 3D and 3E, a set of low profile necking coils 421 are positions between the inner divertors 302 and the formations sections 200.

Axial Plasma Guns

Plasma streams from guns 350 mounted in the divertor chambers 310 of the divertors 300 are intended to improve stability and neutral beam performance. The guns 350 are mounted on axis inside the chamber 310 of the divertors 300 as illustrated in FIGS. 3D and 10 and produce plasma flowing along the open flux lines 452 in the divertor 300 and towards the center of the confinement chamber 100. The guns 350 operate at a high density gas discharge in a washer-stack channel and are designed to generate several kiloamperes of fully ionized plasma for 5 to 10 ms. The guns 350 include a pulsed magnetic coil that matches the output plasma stream with the desired size of the plasma in the confinement chamber 100. The technical parameters of the guns 350 are characterized by a channel having a 5 to 13 cm outer diameter and up to about 10 cm inner diameter and provide a discharge current of 10-15 kA at 400-600 V with a gun-internal magnetic field of between 0.5 to 2.3 T.

The gun plasma streams can penetrate the magnetic fields of the mirror plugs 440 and flow into the formation section 200 and confinement chamber 100. The efficiency of plasma transfer through the mirror plug 440 increases with decreasing distance between the gun 350 and the plug 440 and by making the plug 440 wider and shorter. Under reasonable conditions, the guns 350 can each deliver approximately 10²² protons/s through the 2 to 4 T mirror plugs 440 with high ion and electron temperatures of about 150 to 300 eV and about 40 to 50 eV, respectively. The guns 350 provide significant refueling of the FRC edge layer 456, and an improved overall FRC particle confinement.

To further increase the plasma density, a gas box could be utilized to puff additional gas into the plasma stream from the guns 350. This technique allows a several-fold increase in the injected plasma density. In the FRC system 10, a gas box installed on the divertor 300 side of the mirror plugs 440 improves the refueling of the FRC edge layer 456, formation of the FRC 450, and plasma line-tying.

Given all the adjustment parameters discussed above and also taking into account that operation with just one or both guns is possible, it is readily apparent that a wide spectrum of operating modes is accessible.

Biasing Electrodes

Electrical biasing of open flux surfaces can provide radial potentials that give rise to azimuthal E×B motion that provides a control mechanism, analogous to turning a knob, to control rotation of the open field line plasma as well as the actual FRC core 450 via velocity shear. To accomplish this control, the FRC system 10 employs various electrodes strategically placed in various parts of the machine. FIGS. 3A and 3D depicts biasing electrodes positioned at preferred locations within the FRC system 10.

In principle, there are 4 classes of electrodes: (1) point electrodes 905 in the confinement chamber 100 that make contact with particular open field lines 452 in the edge of the FRC 450 to provide local charging, (2) annular electrodes 900 between the confinement chamber 100 and the formation sections 200 to charge far-edge flux layers 456 in an azimuthally symmetric fashion, (3) stacks of concentric electrodes 910 in the divertors 300 to charge multiple concentric flux layers 455 (whereby the selection of layers is controllable by adjusting coils 416 to adjust the divertor magnetic field so as to terminate the desired flux layers 456 on the appropriate electrodes 910), and finally (4) the anodes 920 (see FIG. 10 ) of the plasma guns 350 themselves (which intercept inner open flux surfaces 455 near the separatrix of the FRC 450). FIGS. 10 and 11 show some typical designs for some of these.

In all cases these electrodes are driven by pulsed or dc power sources at voltages up to about 800 V. Depending on electrode size and what flux surfaces are intersected, currents can be drawn in the kilo-ampere range.

Un-Sustained Operation of FRC System—Conventional Regime

The standard plasma formation on the FRC system 10 follows the well-developed reversed-field-theta-pinch technique. A typical process for starting up an FRC commences by driving the quasi-dc coils 412, 414, 416, 420, 432, 434 and 436 to steady state operation. The RFTP pulsed power circuits of the pulsed power formation systems 210 then drive the pulsed fast reversed magnet field coils 232 to create a temporary reversed bias of about −0.05 T in the formation sections 200. At this point a predetermined amount of neutral gas at 9-20 psi is injected into the two formation volumes defined by the quartz-tube chambers 240 of the (north and south) formation sections 200 via a set of azimuthally-oriented puff-vales at flanges located on the outer ends of the formation sections 200. Next a small RF (˜hundreds of kilo-hertz) field is generated from a set of antennas on the surface of the quartz tubes 240 to create pre-ionization in the form of local seed ionization regions within the neutral gas columns. This is followed by applying a theta-ringing modulation on the current driving the pulsed fast reversed magnet field coils 232, which leads to more global pre-ionization of the gas columns. Finally, the main pulsed power banks of the pulsed power formation systems 210 are fired to drive pulsed fast reversed magnet field coils 232 to create a forward-biased field of up to 0.4 T. This step can be time-sequenced such that the forward-biased field is generated uniformly throughout the length of the formation tubes 240 (static formation) or such that a consecutive peristaltic field modulation is achieved along the axis of the formation tubes 240 (dynamic formation).

In this entire formation process, the actual field reversal in the plasma occurs rapidly, within about 5 μs. The multi-gigawatt pulsed power delivered to the forming plasma readily produces hot FRCs which are then ejected from the formation sections 200 via application of either a time-sequenced modulation of the forward magnetic field (magnetic peristalsis) or temporarily increased currents in the last coils of coil sets 232 near the axial outer ends of the formation tubes 210 (forming an axial magnetic field gradient that points axially towards the confinement chamber 100). The two (north and south) formation FRCs so formed and accelerated then expand into the larger diameter confinement chamber 100, where the quasi-dc coils 412 produce a forward-biased field to control radial expansion and provide the equilibrium external magnetic flux.

Once the north and south formation FRCs arrive near the midplane of the confinement chamber 100, the FRCs collide. During the collision the axial kinetic energies of the north and south formation FRCs are largely thermalized as the FRCs merge ultimately into a single FRC 450. A large set of plasma diagnostics are available in the confinement chamber 100 to study the equilibria of the FRC 450. Typical operating conditions in the FRC system 10 produce compound FRCs with separatrix radii of about 0.4 m and about 3 m axial extend. Further characteristics are external magnetic fields of about 0.1 T, plasma densities around 5×10¹⁹ m⁻³ and total plasma temperature of up to 1 keV. Without any sustainment, i.e., no heating and/or current drive via neutral beam injection or other auxiliary means, the lifetime of these FRCs is limited to about 1 ms, the indigenous characteristic configuration decay time.

Experimental Data of Unsustained Operation—Conventional Regime

FIG. 12 shows a typical time evolution of the excluded flux radius, r_(ΔΦ), which approximates the separatrix radius, r_(s), to illustrate the dynamics of the theta-pinch merging process of the FRC 450. The two (north and south) individual plasmoids are produced simultaneously and then accelerated out of the respective formation sections 200 at a supersonic speed, vz˜250 km/s, and collide near the midplane at z=0. During the collision the plasmoids compress axially, followed by a rapid radial and axial expansion, before eventually merging to form an FRC 450. Both radial and axial dynamics of the merging FRC 450 are evidenced by detailed density profile measurements and bolometer-based tomography.

Data from a representative un-sustained discharge of the FRC system 10 are shown as functions of time in FIGS. 13A, 13B, 13C, and 13D. The FRC is initiated at t=0. The excluded flux radius at the machine's axial mid-plane is shown in FIG. 13A. This data is obtained from an array of magnetic probes, located just inside the confinement chamber's stainless steel wall, that measure the axial magnetic field. The steel wall is a good flux conserver on the time scales of this discharge.

Line-integrated densities are shown in FIG. 13B, from a 6-chord CO₂/He—Ne interferometer located at z=0. Taking into account vertical (y) FRC displacement, as measured by bolometric tomography, Abel inversion yields the density contours of FIG. 13C. After some axial and radial sloshing during the first 0.1 ms, the FRC settles with a hollow density profile. This profile is fairly flat, with substantial density on axis, as required by typical 2-D FRC equilibria.

Total plasma temperature is shown in FIG. 13D, derived from pressure balance and fully consistent with Thomson scattering and spectroscopy measurements.

Analysis from the entire excluded flux array indicates that the shape of the FRC separatrix (approximated by the excluded flux axial profiles) evolves gradually from racetrack to elliptical. This evolution, shown in FIG. 14 , is consistent with a gradual magnetic reconnection from two to a single FRC. Indeed, rough estimates suggest that in this particular instant about 10% of the two initial FRC magnetic fluxes reconnects during the collision.

The FRC length shrinks steadily from 3 down to about 1 m during the FRC lifetime. This shrinkage, visible in FIG. 14 , suggests that mostly convective energy loss dominates the FRC confinement. As the plasma pressure inside the separatrix decreases faster than the external magnetic pressure, the magnetic field line tension in the end regions compresses the FRC axially, restoring axial and radial equilibrium. For the discharge discussed in FIGS. 13A, 13B, 13C, 13D and 14 , the FRC magnetic flux, particle inventory, and thermal energy (about 10 mWb, 7×10¹⁹ particles, and 7 kJ, respectively) decrease by roughly an order of magnitude in the first millisecond, when the FRC equilibrium appears to subside.

Sustained Operation—HPF Regime

The examples in FIGS. 12 to 14 are characteristic of decaying FRCs without any sustainment. However, several techniques are deployed on the FRC system 10 to further improve FRC confinement (inner core and edge layer) to the HPF regime and sustain the configuration.

Neutral Beams

First, fast (H) neutrals are injected perpendicular to B_(z) in beams from the eight neutral beam injectors 600. The beams of fast neutrals are injected from the moment the north and south formation FRCs merge in the confinement chamber 100 into one FRC 450. The fast ions, created primarily by charge exchange, have betatron orbits (with primary radii on the scale of the FRC topology or at least much larger than the characteristic magnetic field gradient length scale) that add to the azimuthal current of the FRC 450. After some fraction of the discharge (after 0.5 to 0.8 ms into the shot), a sufficiently large fast ion population significantly improves the inner FRC's stability and confinement properties (see e.g. M. W. Binderbauer and N. Rostoker, Plasma Phys. 56, part 3, 451 (1996)). Furthermore, from a sustainment perspective, the beams from the neutral beam injectors 600 are also the primary means to drive current and heat the FRC plasma.

In the plasma regime of the FRC system 10, the fast ions slow down primarily on plasma electrons. During the early part of a discharge, typical orbit-averaged slowing-down times of fast ions are 0.3-0.5 ms, which results in significant FRC heating, primarily of electrons. The fast ions make large radial excursions outside of the separatrix because the internal FRC magnetic field is inherently low (about 0.03 T on average for a 0.1 T external axial field). The fast ions would be vulnerable to charge exchange loss, if the neutral gas density were too high outside of the separatrix. Therefore, wall gettering and other techniques (such as the plasma gun 350 and mirror plugs 440 that contribute, amongst other things, to gas control) deployed on the FRC system 10 tend to minimize edge neutrals and enable the required build-up of fast ion current.

Pellet Injection

When a significant fast ion population is built up within the FRC 450, with higher electron temperatures and longer FRC lifetimes, frozen H or D pellets are injected into the FRC 450 from the pellet injector 700 to sustain the FRC particle inventory of the FRC 450. The anticipated ablation timescales are sufficiently short to provide a significant FRC particle source. This rate can also be increased by enlarging the surface area of the injected piece by breaking the individual pellet into smaller fragments while in the barrels or injection tubes of the pellet injector 700 and before entering the confinement chamber 100, a step that can be achieved by increasing the friction between the pellet and the walls of the injection tube by tightening the bend radius of the last segment of the injection tube right before entry into the confinement chamber 100. By virtue of varying the firing sequence and rate of the 12 barrels (injection tubes) as well as the fragmentation, it is possible to tune the pellet injection system 700 to provide just the desired level of particle inventory sustainment. In turn, this helps maintain the internal kinetic pressure in the FRC 450 and sustained operation and lifetime of the FRC 450.

Once the ablated atoms encounter significant plasma in the FRC 450, they become fully ionized. The resultant cold plasma component is then collisionally heated by the indigenous FRC plasma. The energy necessary to maintain a desired FRC temperature is ultimately supplied by the beam injectors 600. In this sense the pellet injectors 700 together with the neutral beam injectors 600 form the system that maintains a steady state and sustains the FRC 450.

CT Injector

As an alternative to the pellet injector, a compact toroid (CT) injector is provided, mainly for fueling field-reversed configuration (FRCs) plasmas. The CT injector 720 comprises a magnetized coaxial plasma-gun (MCPG), which, as shown in FIGS. 21A and 21B, includes coaxial cylindrical inner and outer electrodes 722 and 724, a bias coil positioned internal to the inner electrode 726 and an electrical break 728 on an end opposite the discharge of the CT injector 720. Gas is injected through a gas injection port 730 into a space between the inner and outer electrodes 722 and 724 and a Spheromak-like plasma is generated therefrom by discharge and pushed out from the gun by Lorentz force. As shown in FIGS. 22A and 22B, a pair of CT injectors 720 are coupled to the confinement vessel 100 near and on opposition sides of the mid-plane of the vessel 100 to inject CTs into the central FRC plasma within the confinement vessel 100. The discharge end of the CT injectors 720 are directed towards the mid-plane of the confinement vessel 100 at an angel to the longitudinal axis of the confinement vessel 100 similar to the neutral beam injectors 615.

In an alternative embodiments, the CT injector 720, as shown in FIGS. 23A and 23B, include a drift tube 740 comprising an elongate cylindrical tube coupled to the discharge end of the CT injector 720. As depicted, the drift tube 740 includes drift tube coils 742 positioned about and axially spaced along the tube. A plurality of diagnostic ports 744 are depicted along the length of the tube.

The advantages of the CT injector 720 are: (1) control and adjustability of particle inventory per injected CT; (2) warm plasma is deposited (instead of cryogenic pellets); (3) system can be operated in rep-rate mode so as to allow for continuous fueling; (4) the system can also restore some magnetic flux as the injected CTs carry embedded magnetic field. In an embodiment for experimental use, the inner diameter of an outer electrode is 83.1 mm and the outer diameter of an inner electrode is 54.0 mm. The surface of the inner electrode 722 is preferably coated with tungsten in order to reduce impurities coming out from the electrode 722. As depicted, the bias coil 726 is mounted inside of the inner electrode 722.

In recent experiments a supersonic CT translation speed of up to ˜100 km/s was achieved. Other typical plasma parameters are as follows: electron density ˜5×1021 m−3, electron temperature ˜30-50 eV, and particle inventory of ˜0.5-1.0×1019. The high kinetic pressure of the CT allows the injected plasma to penetrate deeply into the FRC and deposit the particles inside the separatrix. In recent experiments FRC particle fueling has resulted in ˜10-20% of the FRC particle inventory being provide by the CT injectors successfully demonstrating fueling can readily be carried out without disrupting the FRC plasma.

Saddle Coils

To achieve steady state current drive and maintain the required ion current it is desirable to prevent or significantly reduce electron spin up due to the electron-ion frictional force (resulting from collisional ion electron momentum transfer). The FRC system 10 utilizes an innovative technique to provide electron breaking via an externally applied static magnetic dipole or quadrupole field. This is accomplished via the external saddle coils 460 depicted in FIG. 15 . The transverse applied radial magnetic field from the saddle coils 460 induces an axial electric field in the rotating FRC plasma. The resultant axial electron current interacts with the radial magnetic field to produce an azimuthal breaking force on the electrons, F_(θ)=−σV_(eθ)<|B_(r)|²>. For typical conditions in the FRC system 10, the required applied magnetic dipole (or quadrupole) field inside the plasma needs to be only of order 0.001 T to provide adequate electron breaking. The corresponding external field of about 0.015 T is small enough to not cause appreciable fast particle losses or otherwise negatively impact confinement. In fact, the applied magnetic dipole (or quadrupole) field contributes to suppress instabilities. In combination with tangential neutral beam injection and axial plasma injection, the saddle coils 460 provide an additional level of control with regards to current maintenance and stability.

Mirror Plugs

The design of the pulsed coils 444 within the mirror plugs 440 permits the local generation of high magnetic fields (2 to 4 T) with modest (about 100 kJ) capacitive energy. For formation of magnetic fields typical of the present operation of the FRC system 10, all field lines within the formation volume are passing through the constrictions 442 at the mirror plugs 440, as suggested by the magnetic field lines in FIG. 2 and plasma wall contact does not occur. Furthermore, the mirror plugs 440 in tandem with the quasi-dc divertor magnets 416 can be adjusted so to guide the field lines onto the divertor electrodes 910, or flare the field lines in an end cusp configuration (not shown). The latter improves stability and suppresses parallel electron thermal conduction.

The mirror plugs 440 by themselves also contribute to neutral gas control. The mirror plugs 440 permit a better utilization of the deuterium gas puffed in to the quartz tubes during FRC formation, as gas back-streaming into the divertors 300 is significantly reduced by the small gas conductance of the plugs (a meager 500 L/s). Most of the residual puffed gas inside the formation tubes 210 is quickly ionized. In addition, the high-density plasma flowing through the mirror plugs 440 provides efficient neutral ionization hence an effective gas barrier. As a result, most of the neutrals recycled in the divertors 300 from the FRC edge layer 456 do not return to the confinement chamber 100. In addition, the neutrals associated with the operation of the plasma guns 350 (as discussed below) will be mostly confined to the divertors 300.

Finally, the mirror plugs 440 tend to improve the FRC edge layer confinement. With mirror ratios (plug/confinement magnetic fields) in the range 20 to 40, and with a 15 m length between the north and south mirror plugs 440, the edge layer particle confinement time τ_(∥) increases by up to an order of magnitude. Improving τ_(∥) readily increases the FRC particle confinement.

Assuming radial diffusive (D) particle loss from the separatrix volume 453 balanced by axial loss (τ_(∥)) from the edge layer 456, one obtains (2πr_(s)L_(s))(Dn_(s)/δ)=(2πr_(s)L_(s)δ)(n_(s)/τ_(∥)), from which the separatrix density gradient length can be rewritten as δ=(Dτ_(∥))^(1/2). Here r_(s), L_(s) and n_(s) are separatrix radius, separatrix length and separatrix density, respectively. The FRC particle confinement time is τ_(N)=[πr_(s) ²L_(s)<n>]/[(2πr_(s)L_(s))(Dn_(s)/δ)]=(<n>/n_(s))(τ_(⊥)τ_(∥))^(1/2), where τ_(⊥)=a²/D with a=r_(s)/4. Physically, improving τ_(∥) leads to increased δ (reduced separatrix density gradient and drift parameter), and, therefore, reduced FRC particle loss. The overall improvement in FRC particle confinement is generally somewhat less than quadratic because n_(s) increases with τ_(∥).

A significant improvement in τ_(∥) also requires that the edge layer 456 remains grossly stable (i.e., no n=1 flute, firehose, or other MHD instability typical of open systems). Use of the plasma guns 350 provides for this preferred edge stability. In this sense, the mirror plugs 440 and plasma gun 350 form an effective edge control system.

Plasma Guns

The plasma guns 350 improve the stability of the FRC exhaust jets 454 by line-tying. The gun plasmas from the plasma guns 350 are generated without azimuthal angular momentum, which proves useful in controlling FRC rotational instabilities. As such the guns 350 are an effective means to control FRC stability without the need for the older quadrupole stabilization technique. As a result, the plasma guns 350 make it possible to take advantage of the beneficial effects of fast particles or access the advanced hybrid kinetic FRC regime as outlined in this disclosure. Therefore, the plasma guns 350 enable the FRC system 10 to be operated with saddle coil currents just adequate for electron breaking but below the threshold that would cause FRC instability and/or lead to dramatic fast particle diffusion.

As mentioned in the Mirror Plug discussion above, if till can be significantly improved, the supplied gun plasma would be comparable to the edge layer particle loss rate (˜10²²/s). The lifetime of the gun-produced plasma in the FRC system 10 is in the millisecond range. Indeed, consider the gun plasma with density n_(e)˜10¹³ cm⁻³ and ion temperature of about 200 eV, confined between the end mirror plugs 440. The trap length L and mirror ratio R are about 15 m and 20, respectively. The ion mean free path due to Coulomb collisions is λ_(ii)˜6×10³ cm and, since λ_(ii)lnR/R<L, the ions are confined in the gas-dynamic regime. The plasma confinement time in this regime is τ_(gd)˜RL/2V_(s)˜2 ms, where V_(s) is the ion sound speed. For comparison, the classical ion confinement time for these plasma parameters would be τ_(c)˜0.5τ_(ii)(lnR+(lnR)^(0.5))˜0.7 ms. The anomalous transverse diffusion may, in principle, shorten the plasma confinement time. However, in the FRC system 10, if we assume the Bohm diffusion rate, the estimated transverse confinement time for the gun plasma is τ_(⊥)>τ_(gd)˜2 ms. Hence, the guns would provide significant refueling of the FRC edge layer 456, and an improved overall FRC particle confinement.

Furthermore, the gun plasma streams can be turned on in about 150 to 200 microseconds, which permits use in FRC start-up, translation, and merging into the confinement chamber 100. If turned on around t˜0 (FRC main bank initiation), the gun plasmas help to sustain the present dynamically formed and merged FRC 450. The combined particle inventories from the formation FRCs and from the guns is adequate for neutral beam capture, plasma heating, and long sustainment. If turned on at tin the range −1 to 0 ms, the gun plasmas can fill the quartz tubes 210 with plasma or ionize the gas puffed into the quartz tubes, thus permitting FRC formation with reduced or even perhaps zero puffed gas. The latter may require sufficiently cold formation plasma to permit fast diffusion of the reversed bias magnetic field. If turned on at t<−2 ms, the plasma streams could fill the about 1 to 3 m³ field line volume of the formation and confinement regions of the formation sections 200 and confinement chamber 100 with a target plasma density of a few 10¹³ cm⁻³, sufficient to allow neutral beam build-up prior to FRC arrival. The formation FRCs could then be formed and translated into the resulting confinement vessel plasma. In this way the plasma guns 350 enable a wide variety of operating conditions and parameter regimes.

Electrical Biasing

Control of the radial electric field profile in the edge layer 456 is beneficial in various ways to FRC stability and confinement. By virtue of the innovative biasing components deployed in the FRC system 10 it is possible to apply a variety of deliberate distributions of electric potentials to a group of open flux surfaces throughout the machine from areas well outside the central confinement region in the confinement chamber 100. In this way radial electric fields can be generated across the edge layer 456 just outside of the FRC 450. These radial electric fields then modify the azimuthal rotation of the edge layer 456 and effect its confinement via E×B velocity shear. Any differential rotation between the edge layer 456 and the FRC core 453 can then be transmitted to the inside of the FRC plasma by shear. As a result, controlling the edge layer 456 directly impacts the FRC core 453. Furthermore, since the free energy in the plasma rotation can also be responsible for instabilities, this technique provides a direct means to control the onset and growth of instabilities. In the FRC system 10, appropriate edge biasing provides an effective control of open field line transport and rotation as well as FRC core rotation. The location and shape of the various provided electrodes 900, 905, 910 and 920 allows for control of different groups of flux surfaces 455 and at different and independent potentials. In this way a wide array of different electric field configurations and strengths can be realized, each with different characteristic impact on plasma performance.

A key advantage of all these innovative biasing techniques is the fact that core and edge plasma behavior can be effected from well outside the FRC plasma, i.e. there is no need to bring any physical components in touch with the central hot plasma (which would have severe implications for energy, flux and particle losses). This has a major beneficial impact on performance and all potential applications of the HPF concept.

Experimental Data—HPF Operation

Injection of fast particles via beams from the neutral beam guns 600 plays an important role in enabling the HPF regime. FIGS. 16A, 16B, 16C, and 16D illustrate this fact. Depicted is a set of curves showing how the FRC lifetime correlates with the length of the beam pulses. All other operating conditions are held constant for all discharges comprising this study. The data is averaged over many shots and, therefore, represents typical behavior. It is clearly evident that longer beam duration produces longer lived FRCs. Looking at this evidence as well as other diagnostics during this study, it demonstrates that beams increase stability and reduce losses. The correlation between beam pulse length and FRC lifetime is not perfect as beam trapping becomes inefficient below a certain plasma size, i.e., as the FRC 450 shrinks in physical size not all of the injected beams are intercepted and trapped. Shrinkage of the FRC is primarily due to the fact that net energy loss (˜4 MW about midway through the discharge) from the FRC plasma during the discharge is somewhat larger than the total power fed into the FRC via the neutral beams (˜2.5 MW) for the particular experimental setup. Locating the beams at a location closer to the mid-plane of the vessel 100 would tend to reduce these losses and extend FRC lifetime.

FIGS. 17A, 17B, 17C, and 17D illustrate the effects of different components to achieve the HPF regime. It shows a family of typical curves depicting the lifetime of the FRC 450 as a function of time. In all cases a constant, modest amount of beam power (about 2.5 MW) is injected for the full duration of each discharge. Each curve is representative of a different combination of components. For example, operating the FRC system 10 without any mirror plugs 440, plasma guns 350 or gettering from the gettering systems 800 results in rapid onset of rotational instability and loss of the FRC topology. Adding only the mirror plugs 440 delays the onset of instabilities and increases confinement. Utilizing the combination of mirror plugs 440 and a plasma gun 350 further reduces instabilities and increases FRC lifetime. Finally adding gettering (Ti in this case) on top of the gun 350 and plugs 440 yields the best results—the resultant FRC is free of instabilities and exhibits the longest lifetime. It is clear from this experimental demonstration that the full combination of components produces the best effect and provides the beams with the best target conditions.

As shown in FIG. 1 , the newly discovered HPF regime exhibits dramatically improved transport behavior. FIG. 1 illustrates the change in particle confinement time in the FRC system 10 between the conventionally regime and the HPF regime. As can be seen, it has improved by well over a factor of 5 in the HPF regime. In addition, FIG. 1 details the particle confinement time in the FRC system 10 relative to the particle confinement time in prior conventional FRC experiments. With regards to these other machines, the HPF regime of the FRC system 10 has improved confinement by a factor of between 5 and close to 20. Finally and most importantly, the nature of the confinement scaling of the FRC system 10 in the HPF regime is dramatically different from all prior measurements. Before the establishment of the HPF regime in the FRC system 10, various empirical scaling laws were derived from data to predict confinement times in prior FRC experiments. All those scaling rules depend mostly on the ratio R²/ρ_(i), where R is the radius of the magnetic field null (a loose measure of the physical scale of the machine) and ρ_(i) is the ion larmor radius evaluated in the externally applied field (a loose measure of the applied magnetic field). It is clear from FIG. 1 that long confinement in conventional FRCs is only possible at large machine size and/or high magnetic field. Operating the FRC system 10 in the conventional FRC regime CR tends to follow those scaling rules, as indicated in FIG. 1 . However, the HPF regime is vastly superior and shows that much better confinement is attainable without large machine size or high magnetic fields. More importantly, it is also clear from FIG. 1 that the HPF regime results in improved confinement time with reduced plasma size as compared to the CR regime. Similar trends are also visible for flux and energy confinement times, as described below, which have increased by over a factor of 3-8 in the FRC system 10 as well. The breakthrough of the HPF regime, therefore, enables the use of modest beam power, lower magnetic fields and smaller size to sustain and maintain FRC equilibria in the FRC system 10 and future higher energy machines. Hand-in-hand with these improvements comes lower operating and construction costs as well as reduced engineering complexity.

For further comparison, FIGS. 18A, 18B, 18C, and 18D show data from a representative HPF regime discharge in the FRC system 10 as a function of time. FIG. 18A depicts the excluded flux radius at the mid-plane. For these longer timescales the conducting steel wall is no longer as good a flux conserver and the magnetic probes internal to the wall are augmented with probes outside the wall to properly account for magnetic flux diffusion through the steel. Compared to typical performance in the conventional regime CR, as shown in FIGS. 13A, 13B, 13C, and 13D, the HPF regime operating mode exhibits over 400% longer lifetime.

A representative cord of the line integrated density trace is shown in FIG. 18B with its Abel inverted complement, the density contours, in FIG. 18C. Compared to the conventional FRC regime CR, as shown in FIGS. 13A, 13B, 13C, and 13D, the plasma is more quiescent throughout the pulse, indicative of very stable operation. The peak density is also slightly lower in HPF shots—this is a consequence of the hotter total plasma temperature (up to a factor of 2) as shown in FIG. 18D.

For the respective discharge illustrated in FIGS. 18A, 18B, 18C, and 18D, the energy, particle and flux confinement times are 0.5 ms, 1 ms and 1 ms, respectively. At a reference time of 1 ms into the discharge, the stored plasma energy is 2 kJ while the losses are about 4 MW, making this target very suitable for neutral beam sustainment.

FIG. 19 summarizes all advantages of the HPF regime in the form of a newly established experimental HPF flux confinement scaling. As can be seen in FIG. 19 , based on measurements taken before and after t=0.5 ms, i.e., t≤0.5 ms and t>0.5 ms, the flux confinement (and similarly, particle confinement and energy confinement) scales with roughly the square of the electron Temperature (T_(e)) for a given separatrix radius (r_(s)). This strong scaling with a positive power of T_(e) (and not a negative power) is completely opposite to that exhibited by conventional tokomaks, where confinement is typically inversely proportional to some power of the electron temperature. The manifestation of this scaling is a direct consequence of the HPF state and the large orbit (i.e. orbits on the scale of the FRC topology and/or at least the characteristic magnetic field gradient length scale) ion population. Fundamentally, this new scaling substantially favors high operating temperatures and enables relatively modest sized reactors.

With the advantages the HPF regime presents, FRC sustainment or steady state driven by neutral beams and using appropriate pellet injection is achievable, meaning global plasma parameters such as plasma thermal energy, total particle numbers, plasma radius and length as well as magnetic flux are sustainable at reasonable levels without substantial decay. For comparison, FIG. 20 shows data in plot A from a representative HPF regime discharge in the FRC system 10 as a function of time and in plot B for a projected representative HPF regime discharge in the FRC system 10 as a function of time where the FRC 450 is sustained without decay through the duration of the neutral beam pulse. For plot A, neutral beams with total power in the range of about 2.5-2.9 MW were injected into the FRC 450 for an active beam pulse length of about 6 ms. The plasma diamagnetic lifetime depicted in plot A was about 5.2 ms. More recent data shows a plasma diamagnetic lifetime of about 7.2 ms is achievable with an active beam pulse length of about 7 ms.

As noted above with regard to FIGS. 16A, 16B, 16C, and 16D, the correlation between beam pulse length and FRC lifetime is not perfect as beam trapping becomes inefficient below a certain plasma size, i.e., as the FRC 450 shrinks in physical size not all of the injected beams are intercepted and trapped. Shrinkage or decay of the FRC is primarily due to the fact that net energy loss (−4 MW about midway through the discharge) from the FRC plasma during the discharge is somewhat larger than the total power fed into the FRC via the neutral beams (−2.5 MW) for the particular experimental setup. As noted with regard to FIG. 3C, angled beam injection from the neutral beam guns 600 towards the mid-plane improves beam-plasma coupling, even as the FRC plasma shrinks or otherwise axially contracts during the injection period. In addition, appropriate pellet fueling will maintain the requisite plasma density.

Plot B is the result of simulations run using an active beam pulse length of about 6 ms and total beam power from the neutral beam guns 600 of slightly more than about 10 MW, where neutral beams shall inject H (or D) neutrals with particle energy of about 15 keV. The equivalent current injected by each of the beams is about 110 A. For plot B, the beam injection angle to the device axis was about 20°, target radius 0.19 m. Injection angle can be changed within the range 15°-25°. The beams are to be injected in the co-current direction azimuthally. The net side force as well as net axial force from the neutral beam momentum injection shall be minimized. As with plot A, fast (H) neutrals are injected from the neutral beam injectors 600 from the moment the north and south formation FRCs merge in the confinement chamber 100 into one FRC 450.

The simulations that where the foundation for plot B use multi-dimensional hall-MHD solvers for the background plasma and equilibrium, fully kinetic Monte-Carlo based solvers for the energetic beam components and all scattering processes, as well as a host of coupled transport equations for all plasma species to model interactive loss processes. The transport components are empirically calibrated and extensively benchmarked against an experimental database.

As shown by plot B, the steady state diamagnetic lifetime of the FRC 450 will be the length of the beam pulse. However, it is important to note that the key correlation plot B shows is that when the beams are turned off the plasma or FRC begins to decay at that time, but not before. The decay will be similar to that which is observed in discharges which are not beam-assisted—probably on order of 1 ms beyond the beam turn off time—and is simply a reflection of the characteristic decay time of the plasma driven by the intrinsic loss processes.

Plasma Stability and Axial Position Control

Turning now to the systems and methods that facilitate stability of an FRC plasma in both radial and axial directions and axial position control of an FRC plasma along the symmetry axis of an FRC plasma confinement chamber, FIG. 24 shows a simplified scheme to illustrate an example embodiment of an axial position control mechanism 510. A rotating FRC plasma 520 shown within a confinement chamber 100 has a plasma current 522 and an axial displacement direction 524. An equilibrium field (not shown) is produced within the chamber 100 by symmetric current components such as, e.g., the quasi-dc coils 412 (see FIGS. 2 and 3A). The equilibrium field does not produce a net force in the axial displace direction 524, but can be tuned to produce either a transversally/radially or axially stable plasma. For the purposes of the embodiment presented herein, the equilibrium field is tuned to produce a transversally/radially stable FRC plasma 520. As noted above, this results in axial instability and, thus, axial displacement of the FRC plasma 520 in an axial displacement direction 524. As the FRC plasma 520 moves axially it induces current 514 and 516 that are antisymmetric, i.e., in counter directions in the walls of the confinement chamber 100 on each side of the mid-plane of the confinement chamber 100. The FRC plasma 520 will induce these type of current components in both the vessel and also in the external coils. This antisymmetric current components 514 and 516 produce a radial field which interacts with the toroidal plasma current 522 to produce a force that opposes the movement of the FRC plasm 520, and the result of this force is that it slows down plasma axial displacements. These currents 514 and 516 gradually dissipate with time, due to the resistivity of the confinement chamber 100.

Radial field coils 530 and 531 disposed about the confinement chamber 100 on each side of the mid-plane provide additional radial field components that are due to the currents 532 and 534 induced in counter directions in the coils 530 and 531. The radial field coils 530 and 531 may comprise a set of axisymmetric coils that may be positioned internal or external to the containment vessel 100. The radial coils 530 and 531 are shown to be positioned external to the containment vessel 100 similar to the quasi-dc coils 412 (see, FIGS. 2 and 3A). Each of the coils 530 and 531, or sets of coils, may carry a different current than the coils on the opposite side of the mid-plane, but the currents are antisymmetric with respect to the mid-plane of the containment vessel 100 and produce a magnetic field structure with B_(z)≠0, B_(r)=0 along the midplane. The radial field coils 530 and 531 create a supplemental radial field component that interacts with the toroidal plasma current 522 to produce an axial force. The axial force in turn moves the plasma back towards the mid-plane of the confinement chamber 100.

The control mechanism 510 includes a control system configured to act on the radial field coil current in order to expeditiously restore the plasma position towards the mid-plane while minimizing overshooting and/or oscillations around the machine mid-plane. The control system includes a processor operably coupled to the radial field coils 530 and 531, the quasi-dc coils 412, their respective power supplies, and other components such as, e.g., magnetic sensors, providing plasma position, plasma velocity, and active coil current measurements. The processor may be configured to perform the computations and analyses described in the present application and may include or be communicatively coupled to one or more memories including non-transitory computer readable medium. It may include a processor-based or microprocessor-based system including systems using microcontrollers, reduced instruction set computers (RISC), application specific integrated circuits (ASICs), logic circuits, and any other circuit or processor capable of executing the functions described herein. The above examples are exemplary only, and are thus not intended to limit in any way the definition and/or meaning of the term “processor” or “computer.”

Functions of the processor may be implemented using either software routines, hardware components, or combinations thereof. The hardware components may be implemented using a variety of technologies, including, for example, integrated circuits or discrete electronic components. The processor unit typically includes a readable/writeable memory storage device and typically also includes the hardware and/or software to write to and/or read the memory storage device.

The processor may include a computing device, an input device, a display unit and an interface, for example, for accessing the Internet. The computer or processor may include a microprocessor. The microprocessor may be connected to a communication bus. The computer or processor may also include a memory. The memory may include Random Access Memory (RAM) and Read Only Memory (ROM). The computer or processor may also include a storage device, which may be a hard disk drive or a removable storage drive such as a floppy disk drive, optical disk drive, and the like. The storage device may also be other similar means for loading computer programs or other instructions into the computer or processor.

The processor executes a set of instructions that are stored in one or more storage elements, in order to process input data. The storage elements may also store data or other information as desired or needed. The storage element may be in the form of an information source or a physical memory element within a processing machine.

The problem of controlling the position of an axially stable or unstable FRC configuration using the radial field coil actuators is solved using a branch of non-linear control theory known as sliding mode control. A linear function of system states (the sliding surface) acts as the error signal with the desired asymptotically stable (sliding) behavior. The sliding surface is designed using Liapunov theory to exhibit asymptotic stability in a broad range of FRC dynamic parameters. The proposed control scheme can then be used for both axially stable and unstable plasmas without the need to re-tune the parameters used in the sliding surface. This property is advantageous because, as mentioned before, the equilibrium may have to transit between axially stable and axially unstable equilibria on different phases of the FRC discharge.

The configuration of the control scheme 500 is shown in FIG. 25 . The low pass filter restricts the switching frequencies within the desired control bandwidth. A digital control loop requiring sampling and signal transmission with one sample delay is assumed. The error signal (the sliding surface) is a linear combination of coil current, plasma position and plasma velocity. Plasma position and velocity of the plasma are obtained from external magnetic measurements. Currents in the active coil systems can be measured by standard methods.

Coil currents and plasma position are required to implement the position control. Plasma velocity is required to improve performance but is optional. A non-linear function of this error signal (relay control law) generates discrete voltage levels for every pair of power supplies connected to mid-plane symmetric coils. Midplane symmetric coils are feed with relay voltages of same intensity but opposite sign. This creates a radial field component to restore the plasma position towards the mid-plane.

To demonstrate the feasibility of the control scheme, a rigid plasma model is used to simulate the plasma dynamics. The model utilizes a magnet geometry. Plasma current distribution corresponds to axially unstable equilibria with a growth time of 2 ms when only plasma and vessel are considered. The power supplies are assumed to work with discrete voltage levels, typically in 800 V steps.

FIG. 26 shows several plasma control simulations that highlight the relationship between applied voltages to the coils, and the plasma position settling times, along with the required coil peak current and ramp rates to bring back to the mid-plane a plasma that was displaced axially by 20 cm. These sliding mode axial position control simulation examples are run at 0.3 T using four pairs of external trim coils. Four cases are shown corresponding with power supplies with discrete voltage levels in steps of 200 V (solid square), 400V (solid circle), 800 V (solid triangle) and 1600 V (hollow square). For all four cases the control bandwidth is 16 kHz and sampling frequency is 32 kHz. The plasma position (top figure), current in the outermost coil pair (middle) and coil current ramp-rate (bottom) are shown. Plasma displacement is allowed to grow unstable until it reaches 20 cm. At this point the feedback control is applied.

Simulation results indicate that:

-   -   1. To bring the plasma back to the mid-plane within 5 ms (solid         square traces), coil ramp-up rate of 0.5MA/s suffices, requiring         a 200 V power supply.     -   2. To bring the plasma back to the mid-plane within 2.3 ms         (solid circle traces), coil ramp-up rate of 1MA/s suffices,         requiring a 400 V power supply.     -   3. To bring the plasma back to the mid-plane within 1.3 ms         (solid triangle traces), coil ramp-up rate of 2MA/s suffices,         requiring an 800 V power supply.     -   4. To bring the plasma back to the mid-plane within 1.0 ms         (hollow square traces), coil ramp-up rate of 4MA/s suffices,         requiring a 1600 V power supply.

The peak currents for all the trim coils for the third case studied above (the 2MA/s ramp rate case) are also shown in FIG. 27 as function of trim coil position. The sliding mode axial position control simulation examples are run at 0.3 T using four pairs of external trim coils using a power supply with three levels (+800V,0,−800V), a control bandwidth of 16 kHz and a sampling rate of 32 kHz. To bring the plasma back to the mid-plane within 1.3 ms, coil ramp-up rate of 2MA/s is required. The peak current required in all coil pair is less than 1.5 kA. The actual switching frequency required (about 2 kHz) is well below the control system bandwidth

The control system can also be implemented a target surface which is function of coil current and plasma velocity alone, without plasma position. In this case the axial position control loop provides only stabilization of the axial dynamics, but not control. This means that the plasma is in a metastable situation and can drift slowly along its axis. The position control is then provided using an additional feedback loop that controls the plasma gaps between plasma separatrix and vessel, hence it performs plasma shape and position control simultaneously.

Another plasma confinement device where similar control systems are used is the tokamak. To maintain plasma confinement, the plasma current in a tokamak must be kept between a lower and an upper limit that are roughly proportional to plasma density and toroidal field, respectively. To operate at high plasma density plasma current must be increased. At the same time the poloidal field must be kept as low as possible so the q safety factor is above q=2. This is achieved by elongating the plasma along the machine axis direction, allowing to fit large plasma current (and hence allow high plasma density) without increasing the boundary magnetic field above its safety limits. These elongated plasmas are unstable along the machine axis direction (known in tokamak jargon as the vertical direction), and also require plasma stabilization mechanisms. Vertical plasma position control in tokamaks is also restored using a set of radial field coils, so it strongly resembles the RFC position control problem. However the reasons to require stabilization in a tokamak and an FRC are different. In a tokamak plasma vertical instability is a penalty to be paid to operate at large plasma current, which requires plasma elongation to operate with high toroidal field. In the case of the FRC, plasma instability is a penalty to be paid to obtain transverse stability. Tokamaks have toroidal field that stabilizes the configuration, so they don't need transverse stabilization.

The example embodiments provided herein have been described in U.S. Provisional Patent Application No. 62/255,258 and U.S. Provisional Patent Application No. 62/309,344, which applications are incorporated by reference.

The example embodiments provided herein, however, are merely intended as illustrative examples and not to be limiting in any way.

All features, elements, components, functions, and steps described with respect to any embodiment provided herein are intended to be freely combinable and substitutable with those from any other embodiment. If a certain feature, element, component, function, or step is described with respect to only one embodiment, then it should be understood that that feature, element, component, function, or step can be used with every other embodiment described herein unless explicitly stated otherwise. This paragraph therefore serves as antecedent basis and written support for the introduction of claims, at any time, that combine features, elements, components, functions, and steps from different embodiments, or that substitute features, elements, components, functions, and steps from one embodiment with those of another, even if the following description does not explicitly state, in a particular instance, that such combinations or substitutions are possible. Express recitation of every possible combination and substitution is overly burdensome, especially given that the permissibility of each and every such combination and substitution will be readily recognized by those of ordinary skill in the art upon reading this description.

In many instances entities are described herein as being coupled to other entities. It should be understood that the terms “coupled” and “connected” (or any of their forms) are used interchangeably herein and, in both cases, are generic to the direct coupling of two entities (without any non-negligible (e.g., parasitic) intervening entities) and the indirect coupling of two entities (with one or more non-negligible intervening entities). Where entities are shown as being directly coupled together, or described as coupled together without description of any intervening entity, it should be understood that those entities can be indirectly coupled together as well unless the context clearly dictates otherwise.

While the embodiments are susceptible to various modifications and alternative forms, specific examples thereof have been shown in the drawings and are herein described in detail. It should be understood, however, that these embodiments are not to be limited to the particular form disclosed, but to the contrary, these embodiments are to cover all modifications, equivalents, and alternatives falling within the spirit of the disclosure. Furthermore, any features, functions, steps, or elements of the embodiments may be recited in or added to the claims, as well as negative limitations that define the inventive scope of the claims by features, functions, steps, or elements that are not within that scope. 

What is claimed is:
 1. A system for stabilizing a field reversed configuration (FRC) plasma within a confinement chamber comprising a confinement chamber, first and second divertors coupled to first and second ends of the confinement chamber, first and second axial plasma guns operably coupled to the first and second divertors, the first and second formation sections and the confinement chamber, a plurality of neutral atom beam injectors coupled to the confinement chamber and oriented to inject neutral atom beams toward a mid-plane of the confinement chamber at an angle less than normal to a longitudinal axis of the confinement chamber, a magnetic system comprising a plurality of quasi-dc coils positioned around the confinement chamber, the first and second formation sections, and the first and second divertors, first and second set of quasi-dc mirror coils positioned between the confinement chamber and the first and second formation sections, and first and second mirror plugs position between the first and second formation sections and the first and second divertors, a gettering system coupled to the confinement chamber and the first and second divertors, first and second set of radial magnetic field coils configured to generate first and second radial magnetic fields within chamber, and a control system operably coupled to the quasi-dc coils and the first and second radial magnetic field coils, the control system including a processor coupled to a non-transitory memory comprising a plurality of instruction that when executed causes the processor to tune the magnetic field generated by the plurality of quasi-dc coils and the first and second radial field coils to stabilize an FRC plasma in a radial direction normal to a longitudinal axis of the chamber to position the FRC plasma axisymmetric about the longitudinal axis and in an axial direction along the longitudinal axis of the confinement chamber.
 2. The system of claim 1 wherein the control system is configured to tune the magnetic field generated by the plurality of quasi-dc coils to induce stability in the FRC plasma in a radial direction normal to a longitudinal axis of the confinement chamber wherein the FRC plasma is positioned axisymmetric about the longitudinal axis of the confinement chamber, and to induce instability in the FRC plasma in an axial direction along the longitudinal axis of the confinement chamber.
 3. The system of claim 2 wherein the control system is configured to tune the first and second radial magnetic fields generated by the first and second radial coils to interact with the FRC magnetic field positioned about the FRC plasma to induce stability in the FRC plasma in the axial direction along the longitudinal axis of the confinement chamber.
 4. The system of claim 1 wherein the system is configured to generate an FRC plasma and maintain the FRC plasma at or about a constant value without decay while neutral atom beams are injected into the FRC plasma.
 5. The system of claim 3 wherein the first and second radial magnetic fields are antisymmetric about the mid-plane.
 6. The system of claim 1 further comprising first and second diametrically opposed FRC formation sections coupled to the first and second divertors, the formation section comprising modularized formation systems for generating a formation FRC plasma and translating the formation FRC plasma toward a midplane of the confinement chamber.
 7. The system of claim 7 further comprising third and fourth divertors coupled to the first and second diametrically opposed FRC formation.
 8. The system of claim 1 wherein the control system is configured to control the radial electric field profile in an edge layer of the FRC plasma by applying a distribution of electric potential to a group of open flux surfaces of the FRC plasma with biasing electrodes.
 9. The system of claim 1 wherein the gettering system includes one of a Titanium deposition system and a Lithium deposition system.
 10. The system of claim 1 wherein the control system is configured to form a formation FRC plasma in the first and second formation sections and accelerate the formation FRC plasma towards the mid-plane of the chamber to form the FRC plasma.
 11. The system of claim 1 further comprising quasi-dc mirror coils extending about the opposing ends of the confinement chamber generating a mirror magnetic field within opposing ends of the confinement chamber.
 12. The system of claim 1 wherein the control system is configured to monitor the position of the FRC plasma.
 13. The system of claim 12 wherein the control system is configured to monitor the magnetic measurements associated with the FRC plasma.
 14. The system of claim 12 wherein the control system is configured to measure the current in the first and second radial coils.
 15. The system of claim 12 wherein the control system is configured to monitor the velocity of the FRC plasma. 